Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jang, Changheui
Showing results 154 to 213 of 263
| Incorporation of materials’ sensitive simulation technique into the PINTIN-CAM code for integrity of nuclear piping system Jang, Changheui, Pressure Vessels & Piping 2010, 2010-07-20 |
| Influence of delta-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels Byun, Thak Sang; Lach, Timothy G.; Yang, Ying; Jang, Changheui, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp.613 - 624, SPRINGER INTERNATIONAL PUBLISHING AG, 2017-08 |
| Influence of microstructure on hydrothermal corrosion of chemically vapor processed SiC composite tubes Kim, Daejong; Lee, Ho Jung; Jang, Changheui; Lee, Hyeon-Geun; Park, Ji Yeon; Kim, Weon-Ju, JOURNAL OF NUCLEAR MATERIALS, v.492, pp.6 - 13, 2017-08 |
| Integrity of Alumina Catalytic Support Prepared by Anodization in a High Temperature Steam Environment Kim, Chaewon; Kim, Sung Hwan; Subramanian, Gokul Obulan; Jang, Changheui; Park, Keun Man, METALS AND MATERIALS INTERNATIONAL, v.25, no.2, pp.324 - 332, 2019-03 |
| Integrity of Ni-base superalloys for advanced nuclear systems application - environment and materials interaction Jang, Changheui; Kim, D; Kim, D; Kim, M; Sah, I; Ryu, WS; Yoon, DJ, Structural Materials for Innovative Nuclear System (SMINS)-2, 2010-09-01 |
| Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment Lim, Yun Soo; Kim, Sung Woo; Hwang, Seong Sik; Kim, Hong Pyo; Jang, Changheui, CORROSION SCIENCE, v.108, pp.125 - 133, 2016-07 |
| Investigation of the electrical conductivity of sintered monoclinic zirconia (ZrO2) Kwon, Oh Hyun; Jang, Changheui; Lee, Junho; Jeong, Hu Young; Kwon, Young-il; Joo, Jong Hoon; Kim, Hongjin, CERAMICS INTERNATIONAL, v.43, no.11, pp.8236 - 8245, 2017-08 |
| Investigation on corrosion mechanism of Nb-added Zirconium alloy by analysis of electrical conductivity = 전기전도도 분석을 통한 니오비움 첨가 지르코늄합금 부식기구 연구link Kwon, Ohhyun; Jang, Changheui; et al, 한국과학기술원, 2019 |
INVESTIGATION ON THE THERMAL BUTT FUSION PERFORMANCE OF THE BURIED HIGH DENSITY POLYETHYLENE PIPING IN NUCLEAR POWER PLANT Kim, Jong-Sung; Oh, Young-Jin; Choi, Sun-Woong; Jang, Changheui, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.4, pp.1142 - 1153, 2019-07 |
| Irradiation Embrittlement of Cladding and HAZ of RPV Steel Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., International Symposium on Research Reactor and Neutron Science, 2005-04-15 |
| IRRADIATION EMBRITTLEMENT OF CLADDING AND HAZ OF RPV STEEL Lee J.S; Kim I.S; Jang, Changheui; Kimura A, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.5, pp.405 - 410, 2006-08 |
| Irradiation hardening and embrittlement in high-Cr oxide dispersion strengthened steels Oh, S; Lee, JS; Jang, Changheui; Kimura, A, JOURNAL OF NUCLEAR MATERIALS, v.386-88, pp.503 - 506, 2009-04 |
| Korean Nuclear Power Plant Lifetime Improvement Study and Future Plan Jang, Changheui, 12th KAIF/KNS Annual Conference, 1997-04-03 |
| Korean PMMD: Approach and prospect Hwang, I.S.; Kang, S.C.; Hong, J.H.; Jang, Changheui, ANS 2009 Spring Meeting, v.100, pp.411 - 412, 2009-06-14 |
| Korean Status Of Environmental Fatigue Tests Of Structural Materials In A Simulated Primary Coolant System Water Jang, Changheui; Jang, Hun; Hong, Jong-Dae; Kim, Tae Soon, Proceedings of ICAPP 2013, Korea Atomic Energy Research Institute (KAERI), 2013-04-14 |
| Leak Failure Analysis for Reactor Coolant Loop in a Nuclear Power Plant Jang, Changheui, 16th Pacific Basin Nuclear Conference (16PBNC), 2008-10-15 |
| Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel Jeong, IS; Jang, Changheui; Park, JH; Hong, SY; Jin, TE; Yuem, HG; Jeong, SG, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.78, no.2-3, pp.99 - 109, 2001 |
| Life beyond 60 years: Korean perspectives Jang, Changheui; Hwang, II S., 714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, v.2, pp.1557 - 1570, 2009-08-23 |
| Low cycle fatigue behavior of alloy 690 in simulated PWR water-Effects of dynamic strain aging and hydrogen Hong, Jongdae; Lee, Junho; Jang, Changheui; Kim, Tae Soon, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.611, pp.37 - 44, 2014-08 |
| Low cycle fatigue behavior of hot-bent 347 stainless steel in a simulated PWR water environment Lee, Junho; Seo, Myung-Gyu; Hong, Jong-Dae; Kim, Tae Soon; Jang, Changheui, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.30, no.11, pp.4931 - 4936, 2016-11 |
| Low cycle fatigue behavior of hot-bent 347 stainless steels in a simulated PWR environments = 가동 원전 환경에서의 고주파유도가열 배관 벤딩을 적용한 347 스테인리스강의 저주기 피로 거동link Lee, Junho; 이준호; et al, 한국과학기술원, 2016 |
| Low Cycle Fatigue Behaviors of Alloy 690 and 52M in PWR Primary Water Condition Jang, Changheui; Hong, Jong-Dae; Kim, Tae Soon; Lee, Yong Sung, 16th EDM, American Nuclear Society, 2013-08-11 |
| Low Cycle Fatigue Behaviors of Low Alloy Steels and Stainless Steels in Deoxygenated High Temperature Water Jang, Changheui, the 12th International Conference on Pressure Vessel Technology, 2009-09-21 |
| Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310 degrees C deaerated water-fatigue life and dislocation structure development Cho, Hyunchul; Kim, Byoung Koo; Kim, In Sup; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.476, no.1-2, pp.248 - 256, 2008-03 |
| Maintenance Technology Status of Korean Nuclear Power Plants: A Questionnaire Survey Seong, Poong-Hyun; Jang, Changheui; Lee, Jun Seok; Lim, Hyuk Soon; Na, Jang Hwan; Oh, Seong Jong, 한국원자력학회 2005 추계학술대회, 한국원자력학회, 2005-10 |
| Major components life evaluation for nuclear PLIM feasibility study Jang, Changheui, 15th International Conference on Structural Mechanics in Reactor Technology, 1999-08-16 |
| Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel Al Hammadi, Rashid; Yi, Yongsun; Zaki, Wael; Cho, Pyungyeon; Jang, Changheui, NUCLEAR ENGINEERING AND DESIGN, v.301, pp.24 - 31, 2016-05 |
| Mechanical Properties Evaluation in Inconel 82/182 Dissimilar Metal Welds Jang, Changheui, 19th International Conference on Structural Mechanics in Reactor Technology (SMiRT 19), 2007-08-13 |
| Mechanical properties of ion-irradiated stainless steel determined by nanoindentation tests and finite element analyses Sim, Jae Min; Chang, Yoon-Suk; Kong, ByeongSeo; Jang, Changheui, ASME 2020 Pressure Vessels and Piping Conference, PVP 2020, American Society of Mechanical Engineers (ASME), 2020-08-03 |
| Mechanical Properties of Ni-base Superalloys in High Temperature Steam Environments Jang, Changheui; Kim, Donghoon; Sah, Injin; Lee, Ho Jung, SMINS-3, Nuclear Energy Agency (NEA), 2013-10-07 |
| Mechanical Properties of the Diffusion-bonded Ni- and Fe-base Alloys Sah, Injin; Hong, Sunghoon; Jang, Changheui, MST 2013 Conference and Exhibition, The Minerals, Metals & Materials Society (TMS), 2013-10-27 |
| Mechanical Property Changes During Accelerated Thermal Aging Embrittlement Heat Treatment of Cast Stainless Steel, CF-8A Wann, KhingMay; Lee, Joo Suk; Jang, Changheui, 한국원자력학회 2005년도 추계학술발표회 , pp.993 - 994, 한국원자력학회, 2005-10 |
| Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel Jang, Changheui; Lee, Jounghoon; Kim, Jong Sung; Jin, Tae Eun, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.85, no.9, pp.635 - 646, 2008-09 |
| Metal corrosion resistances in high temperature hydriodic aicd gas environment for SI cycle Jang, Changheui; Jin Young Choi; Young Soo Kim; In Jin Sah; No, Hee Cheon, 2012 American Nuclear Society Winter Meetings, American Nuclear Society, 2011-11-14 |
| Microstructure and creep resistance of a diffusionally aluminized Ni-base superalloy Sah, Injin; Kim, Sung Hwan; Jang, Changheui, METALS AND MATERIALS INTERNATIONAL, v.22, no.6, pp.1033 - 1040, 2016-11 |
| Microstructure and hydride embrittlement of zirconium model alloys containing niobium and tin Oh, Seung Jin; Jang, Changheui; Kim, Jun Hwan; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.528, no.10-11, pp.3771 - 3776, 2011-04 |
| Microstructure and Tensile Properties of Diffusion Bonded Austenitic Fe-Base Alloys-Before and After Exposure to High Temperature Supercritical-CO2 Kim, Sung Hwan; Cha, Ji-Hwan; Jang, Changheui; Sah, Injin, METALS, v.10, no.4, 2020-04 |
| Microstructure evolution of a Ni-Cr-W superalloy during long-term aging at high temperatures Lee, Ho Jung; Kim, Hyunmyung; Kim, Donghoon; Jang, Changheui, MATERIALS CHARACTERIZATION, v.106, pp.283 - 291, 2015-08 |
| Microstructures, tensile properties and corrosion behaviors of Fe20Cr25NiNb stainless steels with different Al contents in supercritical carbon dioxide Chen, Hongsheng; Luo, Jiandong; Zhang, Tengfei; Jang, Changheui; Tang, Rui; Dong, Baojun; Li, Jin; et al, JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T, v.23, pp.5246 - 5259, 2023-03 |
| Multiscale simulations for estimating mechanical properties of ion irradiated 308 based on microstructural features Kwak, Dong-Hyeon; Sim, Jae Min; Chang, Yoon-Suk; Kong, Byeong Seo; Jang, Changheui, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.8, pp.2823 - 2834, 2023-08 |
| Nano-scale characterization of microstructure and deformation behavior for δ-ferrite in thermally aged/irradiated stainless steel weld = 열취화 및 조사취화된 스테인리스강 용접부 페라이트에 대한 나노스케일 미세조직 특성 및 변형거동에 대한 연구link Kong, Byeong Seo; Jang, Changheui; et al, 한국과학기술원, 2023 |
| Nano-Structured Columnar Tungsten Coating for Plasma Facing Component in Nuclear Fusion Application Lee, Ho Jung; Kim, Hyunmyung; Jang, Changheui, 2013 AEPSE, AJC-APSE (Asian Joint Committee for Applied Plasma Science and Engineering), 2013-08-25 |
| On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors Xiao, Qian; Kim, Chaewon; Jang, Changheui; Jeong, Chaewon; Kim, Hyunmyung; Chen, Junjie; Heo, Woong, JOURNAL OF NUCLEAR MATERIALS, v.557, 2021-12 |
| On the use of non-destructive, gigahertz ultrasonics to rapidly screen irradiated steels for swelling resistance Almousa, Nouf; Dacus, Benjamin; Woller, Kevin B.; Shin, Ji Ho; Jang, Changheui; Shao, Lin; Garner, Frank A.; et al, MATERIALS CHARACTERIZATION, v.174, pp.111017, 2021-04 |
| Oxidation behavior of alumina-forming duplex stainless steels in high temperature steam environments = 고온 수증기 환경에서 알루미나 형성 듀플렉스 스테인리스강의 산화 거동link Kim, Chaewon; Jang, Changheui; et al, 한국과학기술원, 2019 |
| Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor Chen, Hongsheng; Wang, Haibo; Sun, Qingzhu; Long, Chongsheng; Wei, Tianguo; Kim, Sung Hwan; Chen, Junjie; et al, CORROSION SCIENCE, v.145, pp.90 - 99, 2018-12 |
| Oxidation behavior of high-strength FeCrAl alloys in a high-temperature supercritical carbon dioxide environment Chen, Hongsheng; Kim, Sung Hwan; Long, Chongsheng; Kim, Chaewon; Jang, Changheui, PROGRESS IN NATURAL SCIENCE-MATERIALS INTERNATIONAL, v.28, no.6, pp.731 - 739, 2018-12 |
| Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments Jang, Changheui, IUMRS 11th International Conference in Asia, 2010-09-28 |
| Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments Jang, Changheui; Lee, Daejin; Kim, Daejong, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.85, no.6, pp.368 - 377, 2008-06 |
| Oxidation Characteristics and Oxide Layer Evolution of Alloy 617 and Haynes 230 at 900 A degrees C and 1100 A degrees C Kim, Daejong; Jang, Changheui; Ryu, Woo Seog, OXIDATION OF METALS, v.71, no.5-6, pp.271 - 293, 2009-06 |
| Oxidation characteristics of Nickel-base superalloys at high temperature in air and helium atmospheres Lee, D.; Kim, D.; Jang, Changheui, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, The Nuclear Renaissance at Work, pp.2360 - 2365, 2007-05-13 |
| Oxidation Effects on the Strength and Fracture Toughness of the Selected Nuclear Graphite Grades at 600 ¡ÆC Kim, Byung Jun; Kim, Daejong; Jang, Changheui; Chi, Se-Hwan, CARBON 2007, 2007-07-18 |
| Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500-1500 degrees C in steam Kim, Chaewon; Tang, Chongchong; Grosse, Mirco; Maeng, Yunhwan; Jang, Changheui; Steinbrueck, Martin, JOURNAL OF NUCLEAR MATERIALS, v.564, 2022-06 |
| Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment Lee, Daejin; Lee, Sanggyu; Jang, Changheui, Korea Nuclear Society, Korea Nuclear Society, 2006 |
| Passivity breakdown of 316L stainless steel during potentiodynamic polarization in NaCl solution Al Saadi, Sara; Yi, Yongsun; Cho, Pyungyeon; Jang, Changheui; Beeley, Philip, CORROSION SCIENCE, v.111, pp.720 - 727, 2016-10 |
| Performance of a dual-process PVD/PS tungsten coating structure under deuterium ion irradiation Kim, Hyunmyung; Lee, Ho Jung; Kim, Sung Hwan; Song, Jae-Min; Jang, Changheui, FUSION ENGINEERING AND DESIGN, v.109, pp.353 - 358, 2016-11 |
| PFM APPLICATION FOR THE PWSCC INTEGRITY OF Ni-BASE ALLOY WELDS - DEVELOPMENT AND APPLICATION OF PINEP-PWSCC Hong, Jong-Dae; Jang, Changheui; Kim, Tae Soon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.44, no.8, pp.961 - 970, 2012-12 |
| Phase stability and thermal aging behavior in high-strength Fe-Ni-Cr-Al alloys = 고강도 Fe-Ni-Cr-Al 합금 내 상 안정성 및 열 시효 특성link Kim, Chaewon; 김채원; et al, 한국과학기술원, 2023 |
| Plant Specific PTS Analysis of Kori Unit 1 Jang, Changheui, IAEA Specialist Meeting 1997, 1997-05-06 |
| Plasma thermal performance of a dual-process PVD/PS tungsten coating on carbon-based panels for nuclear fusion application Kim, Hyunmyung; Lee, Ho Jung; Kim, Sung Hwan; Jang, Changheui, FUSION ENGINEERING AND DESIGN, v.109, pp.590 - 595, 2016-11 |
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